Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 30

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Intelligible seminar of fusion reactors, 10; Remote maintenance robot for in-vessel components, Advanced robot technology for handling large-heavy components with high positioning accuracy

Shibanuma, Kiyoshi

Nihon Genshiryoku Gakkai-Shi, 47(11), p.761 - 767, 2005/11

In-vessel components such as blanket and divertor of the fusion reactor are activated by neutron produced during fusion reaction. Gamma radiation will be about 500 MGy/h in maximum after fusion reaction. When the components are failed or troubled in the vessel, the maintenence has to be carried out by the robot because the human cannot be close inside the vessel. The required functions and present R&D status of the typical robots applied to ITER are introduced as examples of robots maintaining the in-vessel components of the fusion reactor.

JAEA Reports

Research and development of remote maintenance equipment for ITER divertor maintenance

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka

JAERI-Tech 2004-071, 85 Pages, 2005/02

JAERI-Tech-2004-071.pdf:4.81MB

To facilitate easy maintainability, the ITER divertor is divided into 60 cassettes, which are transported for replacement using the remote equipments. The cassette of 25 tons has to be transported and installed with a positioning accuracy less than 2 mm in the limited space under the intense gamma radiation field. Based on these requirements, the following design and tests were performed. (1) Link mechanism was studied to apply to the transportation. A compact mechanism with links is designed through the optimization of the link angle taking account of space requirement and force efficiency. The lifting capacity of 30 tons has been demonstrated. (2) Compact link mechanism was also studied to apply for locking of the cassette. The final positioning accuracy of 0.03 mm for installation from the initial positioning error of 5 mm has been demonstrated. (3) Sensor-based control of the remote equipment was tested using simple sensors. It is found that the positioning accuracy of 0.16 mm has been achieved and this value is sufficient.

JAEA Reports

Conceptual design of cesium removal device for ITER NBI maintenance

Oka, Kiyoshi; Shibanuma, Kiyoshi

JAERI-Tech 2003-004, 57 Pages, 2003/03

JAERI-Tech-2003-004.pdf:2.36MB

Cesium is required in order to generate a stable negative ion of hydrogen in an ion source of the neutral beam injector (NBI), which is one of the plasma-heating devices for International Thermonuclear Experimental Reactor (ITER). After long time operation of NBI, the cesium deposits to the insulators supporting the electrode. Due to the deterioration of the insulation resistance, the continuous operation of the NBI will be difficult. In addition, the NBI device is activated by neutron from D-T plasma, so that a periodic removal and cleaning of the cesium on the insulators by remote handling is required. A study of the cesium removal scenario and device is therefore required considering remote handling. In this report, a cesium removal procedure and conceptual design of the cesium removal device using laser ablation technique are studied, and the feasibility of laser ablation is shown.

Journal Articles

Rail deployment and storage procedure and test for ITER blanket remote maintenance

Kakudate, Satoshi; Shibanuma, Kiyoshi

Fusion Engineering and Design, 65(1), p.133 - 140, 2003/01

 Times Cited Count:11 Percentile:59.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Remote handling systems for ITER

Honda, Tsutomu*; Hattori, Yukiya*; Holloway, C.*; Martin, E.*; Matsumoto, Yasuhiro*; Matsunobu, Takashi*; Suzuki, Toshiyuki*; Tesini, A.*; Baulo, V.*; Haange, R.*; et al.

Fusion Engineering and Design, 63-64, p.507 - 518, 2002/12

 Times Cited Count:16 Percentile:69.75(Nuclear Science & Technology)

The requirement to reduce the construction cost for ITER as compared with the 1998 ITER design, has led to a reduction in the size of the ITER machine and a number of design changes which have an impact on the remote maintenance of ITER. Major components to be considered for remote handling (RH) include the divertor cassettes, shield blanket modules, neutral beamline components, as well as in-port components, which are integrated with the port shield plug such as auxiliary heating equipment, limiters and test blanket modules. The design of the following equipment has been adapted for the smaller machine with reduced access space for the RH equipment: the RH equipment used for the in-vessel RH operationsto be deployed from the casks, the RH equipment that is used to remove the in-port assemblies (port plugs), as well as the remotely operated casks, which can be attached to and removed from vacuum vessel ports by using double -door systems. Defective components are loaded in transfer casks and moved to the hot cell facility by means of a remotely-operated air floatation system attached underneath the cask, where they dock against identical port interfaces and unload the component for remote refurbishment and/or waste storage.

Journal Articles

Evaluation of shutdown $$gamma$$-ray dose rates around the duct penetration by three-dimensional Monte Carlo decay $$gamma$$-ray transport calculation with variance reduction method

Sato, Satoshi; Iida, Hiromasa; Nishitani, Takeo

Journal of Nuclear Science and Technology, 39(11), p.1237 - 1246, 2002/11

 Times Cited Count:27 Percentile:83.19(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Remote maintenance technology for ITER

Kakudate, Satoshi; Shibanuma, Kiyoshi

Kensa Gijutsu, 7(11), p.28 - 33, 2002/11

no abstracts in English

Journal Articles

Development of port plug handling tractor for ITER

Ise, Hideo*; Izaki, Makoto*; Oishi, Haruo*; Mori, Seiji*; Ako, Kentaro*; Moriyama, Hisashi*; Kagaya, Hiroaki*; Kobayashi, Masami*; Taguchi, Ko*; Shibanuma, Kiyoshi

FAPIG, (159), p.10 - 14, 2001/11

no abstracts in English

JAEA Reports

Design of remote handling equipment for the ITER NBI

Oka, Kiyoshi; Tada, Eisuke

JAERI-Tech 99-055, 138 Pages, 1999/08

JAERI-Tech-99-055.pdf:4.49MB

no abstracts in English

JAEA Reports

Development of pipe welding, cutting & inspection tools for the ITER blanket

Oka, Kiyoshi; *; *; *; Takahashi, Hiroyuki*; Tada, Eisuke

JAERI-Tech 99-048, 222 Pages, 1999/07

JAERI-Tech-99-048.pdf:24.01MB

no abstracts in English

JAEA Reports

Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER, 2

*; Obara, Kenjiro; Tada, Eisuke; Morita, Yosuke; Yagi, Toshiaki; *

JAERI-Tech 99-029, 36 Pages, 1999/03

JAERI-Tech-99-029.pdf:3.25MB

no abstracts in English

Journal Articles

Development of blanket and divertor remote maintenance for ITER

Nakahira, Masataka; Kakudate, Satoshi; Oka, Kiyoshi; Takeda, Nobukazu; *; *; *; Tada, Eisuke; Shibanuma, Kiyoshi; T.Burgess*; et al.

Fusion Technology, 34(3), p.1160 - 1164, 1998/11

no abstracts in English

Journal Articles

Performance test of divertor cassette transporters for ITER

Takeda, Nobukazu; *; *; Oka, Kiyoshi; Kakudate, Satoshi; Tada, Eisuke; E.Martin*; C.Damiani*; G.Cerdan*

Fusion Technology 1998, 2, p.1099 - 1102, 1998/00

no abstracts in English

Journal Articles

Remote maintenance development for ITER

Tada, Eisuke; Shibanuma, Kiyoshi

J. Robot. Mechatron., 10(2), p.71 - 77, 1998/00

no abstracts in English

Journal Articles

Development of radiation hardness components for ITER remote maintenance

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; Yagi, Toshiaki; Morita, Yosuke

J. Robot. Mechatron., 10(2), p.121 - 132, 1998/00

no abstracts in English

Journal Articles

Development of thick wall welding and cutting tools for ITER

Nakahira, Masataka; *; *; Koizumi, Koichi

J. Robot. Mechatron., 10(2), p.116 - 120, 1998/00

no abstracts in English

Journal Articles

Development of divertor remote maintenance system

Takeda, Nobukazu; Oka, Kiyoshi; *; *

J. Robot. Mechatron., 10(2), p.88 - 95, 1998/00

no abstracts in English

Journal Articles

Development of blanket remote maintenance system

Kakudate, Satoshi; Nakahira, Masataka; Oka, Kiyoshi; *

J. Robot. Mechatron., 10(2), p.78 - 87, 1998/00

no abstracts in English

Journal Articles

Measurement and control system for ITER remote maintenance equipment

Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; *; *

J. Robot. Mechatron., 10(2), p.139 - 145, 1998/00

no abstracts in English

Journal Articles

Development of ITER in-vessel viewing and metrology systems

Obara, Kenjiro; Kakudate, Satoshi; Nakahira, Masataka; *

J. Robot. Mechatron., 10(2), p.96 - 103, 1998/00

no abstracts in English

30 (Records 1-20 displayed on this page)